Published May 2016 | Version v1
Miscellaneous

Effects of Thermal Aging on Type 316H Stainless Steel for Reactor Vessel

  • 1. KAERI, Daejeon (Korea, Republic of)

Description

Type 316H stainless steel is a prime candidate for reactor vessel material of sodium-cooled fast reactor (SFR) which has been developed as one of the Gen IV nuclear reactors in Korea. The reactor vessel steel will be exposed to higher temperature for an extended design life time. It is known that austenitic stainless steel such as Type 316H stainless steel shows excellent toughness and adequate strength at a moderate temperature. However, the previous researches reported the mechanical properties of Type 316H stainless weld would be deteriorated by the aging at the elevated temperature range.

Part of:
Proceedings of the KNS 2016 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2016 spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2016 spring meeting of the KNS
Dates
11-13 May 2016
Place
Jeju (Korea, Republic of)

Optional Information

Notes
11 refs, 4 figs, 2 tabs